ML20093C891
| ML20093C891 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 09/24/1984 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20093C887 | List: |
| References | |
| NUDOCS 8410100780 | |
| Download: ML20093C891 (2) | |
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SAFETY EVALUATION REPORT RELATED TO AMEND!!ENT NO. 1 TO FACILITY OPERATING LICENSE NPF-24 CATAWBA NUCLEAR STATION, UNIT 1 l
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INTRODUCTION l-On July 18, 1984, the U.S. Nuclear Regulatory Commission issued Facility Operating License NPF-24, together with Technical Specifications and other attachments, authorizing fuel loading and precriticality testing for the Catawba Nuclear Station, Unit 1.
The Technical Specifications included surveillance requirements to demonstrate operability of the auxiliary feedwater (AFW) systen, in part, by periodic testing of AFU pumps using a test loop of small diameter piping. - Acceptance criteria for these periodic tests are specified as a minimum value of the total Jynamic head to be developed et a specified r'inirun flow. The acceptance criteria in Technical Spccification 4.7.1.2.1,.as issued, are based upon nominal design parameters for the AFW system specified by Westinghouse on"the basis of providing adequate protection for the core and to assure orderly cooldown. These nominal design parameters are in excess of the require-ments ' assumed for ths limiting safety analyses in thapter 15 of the FSAR.
By letters dated July 31, August 17, 24 and 29,1984, the licensee stated
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that the preoperational functional tests conducted on the AFW system revealed that the acceptance criteria in the surveillance requirements of the current Technical Specification can not.be met and requested that the criteria be changed to be based upon the minimum flow values established during testing and determined to envelope flow requirements for safety analyses.
II.
EJALUATION The AFW system for Catawba Unit 1 consists of two electric motor-driven pumps and one turbine-driven pump. The acceptancg. criteria in Specifi-cation 4.7.1.2.la.1 for periodic testing of each motor-driven AFW pump are changed to require development of a total dynamic head of greater than or equal to 3470 feet at a flow of greater than er equal to 400 gpn, rather than a total dynamic head greater than or equal to 3210 feet at a flow of greater than or equal to 500 gpm,Similarly, the total dynamic head in Specification 4.7.1.2.la.2 to be developed by the turbine-driven pump when the secondary steam supply pressure is greater than 600 psig and the AFW pump turbine is operating at 3600 rpm, is changed to be greater than or eoual to 3550 feet at a flow of greater than or equal to 200 gpn. rather than a total dynar,ic head of greatr:r than or ecual to 3217 feet at a flow of greater than or equal to 1000 ppm. The associated bases 3/4.7.1.2 are changed to reflect that a feedvater line break accident, rather than a total less of offsite power transient, is the limiting event with respect to system flow capacity.
8410100780 840924 PDR ADOCK 05000 P
- 70-By letters dated July 31, August 17, 24 and 29, 1984, the licensee has confirmed that testing each AFW pump through the test loop to verify a minimum flow of 400 gpm rather thar. 500 gpm as previously indicated ersures that the ArW syster is capable of supplying at least 492 spm to at icast two steam gencrators for core protection and decay heat removal ur. der required design basis accident and transient conditicns ccuplec with a single failure.
The staff finds that 492 gpm is the limiting flow value assumed by the licensee in FSAR Chapter 15 safety analyses for Catawba and approved by the staff in the SER.
Therefore, the staff con-cludes that the proposed Technical Specification change is consistent with the safety analyses, and is acceptable.
III.
ENVIRONMENTAL CONSIDERATION This amendment involves a change in the use of a facility component located within the restricted area as defined irr 10 CFR Part 20.
The staff has determined that the amendment invclves no significant increase in the amounts, and no significan change in the types, of any effluents that may be released offsite, and that there is no significant inc'rease in individual or cumulative occupational radiation exposure.
The Commis-sion has previously issued a proposed finding that this amendment involves
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no significant hazards consideration and there has been no public comment on such finding. Accordingly, this amendment meets the eligibility
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criteria for categorical exclusion seti forth in-10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environ-mental assessment need be prepared in connectio.n with the issuance of this amendment.
IV.
CONCLUSION The Commission made a proposed determination that the amendment involves no significant hazards consideration which was published in the Federal Register (49 FR 33068) on August 20, 1984, and consulted with the state of South Carolina.
No public comments were received, and the state of South Carolina did not have any comments.
In cenclusion, the staff finds the proposed changes to the plant Technical Specifications to be acceptable and based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered'by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commis-sion's regulations and the issuance of the amendment will not be ininical to the common defense and security or to the health and safety of the public.
Principal Contributors:
D. Hood, Licensing Branch No. 4, DL A. Singh, Auxiliary Systems Branch, DSI Datec: September 24, 1984
E Septemb2r 24, 1984 AMENDMENT NO. 1 TO FACILITY OPERATING LICENSE NPF 24 - CATAWBA NUCLEAR STATION, UNIT 1-DISTRIJUTION:
t No. 50-413 NRC PDR Local PDR PRC System J
NSIC LB #4 r/f E. Adensam K. Jabbour M. Duncan Attorney, OELD R. Diggs, ADM T.Barnhart(4)
ACRS(16)
E. L. Jordan, DEQA:I&E J. N. Grace, DRP:I&E L. J. Harmon, I&E File D. Brinkman
- 0. Parr A. Singh 1
l l
DE3IGNATI:D ORICIITAL' M.
Certified By,
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